Number 1 | Number 2 | Number 3 | Number 4 | Number 5 | Number 6
Liquid Metal Breeder Reactor (LIMB) Nuclear Evaluation
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 13-24
Technical Paper / dx.doi.org/10.13182/NT65-A20459
Experience with High Pressure Heavy-Water Systems at NPD
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 25-32
Technical Paper / dx.doi.org/10.13182/NT65-A20460
Excursion-Limiting Fuse for the Mixed Spectrum Critical Assembly
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 33-38
Technical Paper / dx.doi.org/10.13182/NT65-A20461
Effects of 1.0% Superimposed Mean Strain on the Bending Fatigue Strength of Zircaloy-4
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 39-48
Technical Paper / dx.doi.org/10.13182/NT65-A20462
Analysis of a Radioisotope Thrustor-Auxiliary Power Unit
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 49-54
Technical Paper / dx.doi.org/10.13182/NT65-A20463
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 55-61
Technical Paper / dx.doi.org/10.13182/NT65-A20464
Void-Fraction Measurements in Cavitating Mercury
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 62-68
Technical Paper / dx.doi.org/10.13182/NT65-A20465
Out-of-Pile Steam-Fraction Determination by Neutron-Beam Attenuation
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 69-75
Technical Paper / dx.doi.org/10.13182/NT65-A20466
The Education, Experience, Training, and Certification of Reactor Operators at AEC-Owned Reactors
Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 76-81
Technical Paper / dx.doi.org/10.13182/NT65-A20467
The Settled-Bed Fast-Reactor Concept—1 000-MWe Reactor Design
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 107-130
Technical Paper / dx.doi.org/10.13182/NT65-A20478
Fuel Management for an Intermediate Power Research Reactor
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 131-135
Technical Paper / dx.doi.org/10.13182/NT65-A20479
Production of the Heaviest Elements by Multiple Neutron Capture
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 136-144
Technical Paper / dx.doi.org/10.13182/NT65-A20480
The Radioisotope-Powered Bimetallic-Disk Engine
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 145-150
Technical Paper / dx.doi.org/10.13182/NT65-A20481
Reactor Production of 109 Cd: Isotopic Composition and Use as an X-Ray Source
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 151-154
Technical Paper / dx.doi.org/10.13182/NT65-A20482
Electrodeposition of 99Tc Metal
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 155-157
Technical Paper / dx.doi.org/10.13182/NT65-A20483
Vacuum Distillation of Magnesium Metal
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 158-159
Technical Paper / dx.doi.org/10.13182/NT65-A20484
Effect of Elevated-Temperature Irradiation on Hastelloy N
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 160-167
Technical Paper / dx.doi.org/10.13182/NT65-A20485
Behavior of Uranium Sulfide Fast-Reactor-Type Fuel Specimens Under Transient Heating in Treat
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 168-175
Technical Paper / dx.doi.org/10.13182/NT65-A20486
Radiation Exposures in Fabricating 233U-Th Fuels
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 176-178
Technical Paper / dx.doi.org/10.13182/NT65-A20487
Determination of Zirconium by Activation and Chemical Separation of 97Nb
Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 179-183
Technical Paper / dx.doi.org/10.13182/NT65-A20488
N S Savannah Containment Integrity, Its Measurement and Improvement
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 213-218
Technical Paper / dx.doi.org/10.13182/NT65-A20504
Head-end Dissolution for UC Processes and UC-PuC Reactor Fuels
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 219-224
Technical Paper / dx.doi.org/10.13182/NT65-A20505
The Evaluation and Measurement of Reactor-Safety Performance
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 225-229
Technical Paper / dx.doi.org/10.13182/NT65-A20506
Fabrication of Radioactive Samples for Cross-Section Measurements
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 230-234
Technical Paper / dx.doi.org/10.13182/NT65-A20507
General Corrosion of Incoloy-800® in Simulated Superheat Reactor Environment
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 235-245
Technical Paper / dx.doi.org/10.13182/NT65-A20508
Corrosion-Rate-Law Considerations in Superheated Steam
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 246-251
Technical Paper / dx.doi.org/10.13182/NT65-A20509
The Failure of Stressed Zircaloy in Aqueous Chloride Solutions
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 252-258
Technical Paper / dx.doi.org/10.13182/NT65-A20510
Technique for Optimizing the Composition of Regenerating-Neutron-Flux Monitors
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 259-266
Technical Paper / dx.doi.org/10.13182/NT65-A20511
Continuous On-reactor Measurement of Instantaneous Corrosion Rates
Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 267-270
Technical Paper / dx.doi.org/10.13182/NT65-A20512
Engineering Development of a Fluid-bed Fluoride Volatility Process I Bench-Scale Studies
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 293-300
Technical Paper / dx.doi.org/10.13182/NT65-A20525
Engineering Development of a Fluid-bed Fluoride Volatility Process II Pilot-Scale Studies
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 301-309
Technical Paper / dx.doi.org/10.13182/NT65-A20526
Hydrogen Reduction of Pu(IV) to Pu(III)
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 310-311
Technical Paper / dx.doi.org/10.13182/NT65-A20527
Neutron and Gamma-Ray Die-Away in a Heterogenous System
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 312-321
Technical Paper / dx.doi.org/10.13182/NT65-A20528
Design and Economic Study of a Gas-phase Chemonuclear Ozone Process
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 322-326
Technical Paper / dx.doi.org/10.13182/NT65-A20529
244Cm Production and Separation—Status of the Pilot Production Program at Savannah River
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 327-336
Technical Paper / dx.doi.org/10.13182/NT65-A20530
Displacement Spike Effects in Copper-rich Copper-Iron Alloys
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 337-347
Technical Paper / dx.doi.org/10.13182/NT65-A20531
Preparation of PuC Pellets by Vacuum Sintering
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 348-355
Technical Paper / dx.doi.org/10.13182/NT65-A20532
A Three-Decade Exponential Current Generator for Testing Reactor Period Meters
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 356-358
Technical Paper / dx.doi.org/10.13182/NT65-A20533
A Comparison of Shielding Calculations with Absolute Measurements in Massive Shields
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 359-374
Technical Paper / dx.doi.org/10.13182/NT65-A20534
Microdetermination of Ruthenium in Uranium Compounds
Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 375-380
Technical Paper / dx.doi.org/10.13182/NT65-A20535
Ordered Packed-Bed Fuel Elements
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 405-411
Technical Paper / dx.doi.org/10.13182/NT65-A20549
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Page 412
Technical Paper / dx.doi.org/10.13182/NT65-A20550
Stainless-Steel-Clad Fuel Rod Failures
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 413-418
Technical Paper / dx.doi.org/10.13182/NT65-A20551
Evaluation of Highly Irradiated Yankee Fuel Cladding
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 419-424
Technical Paper / dx.doi.org/10.13182/NT65-A20552
Performance of Thin-Walled Stainless-Steel-Clad Fuel Rods
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 425-431
Technical Paper / dx.doi.org/10.13182/NT65-A20553
Boron Stainless-Steel Fuel-Element Cladding in the Indian Point Reactor
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 432-438
Technical Paper / dx.doi.org/10.13182/NT65-A20554
Fatigue and Burst Tests on Irradiated In-Pile Stainless-Steel Pressure Tubes
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 439-445
Technical Paper / dx.doi.org/10.13182/NT65-A20555
Corrosion Product Behavior in Stainless-Steel-Clad Water Reactor Systems
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 446-452
Technical Paper / dx.doi.org/10.13182/NT65-A20556
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 453-461
Technical Paper / dx.doi.org/10.13182/NT65-A20557
Radiation Effects on the Mechanical Properties and Microstructure of Type-304 Stainless Steel
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 462-477
Technical Paper / dx.doi.org/10.13182/NT65-A20558
Influence of Preirradiation Heat Treatment on the Postirradiation Ductility of Stainless Steel
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 478-483
Technical Paper / dx.doi.org/10.13182/NT65-A20559
Inhibition of Chloride Stress Corrosion Cracking of Austenitic Stainless Steel
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 484-489
Technical Paper / dx.doi.org/10.13182/NT65-A20560
Formation of Cyanide in Liquid Sodium
Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 490-492
Technical Paper / Technical Note / dx.doi.org/10.13182/NT65-A20561
Liquid-Metal Boiling Heat Transfer
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 521-537
Technical Paper / dx.doi.org/10.13182/NT65-A20579
Effective Resonance Temperature Correlation of UO2
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 538-545
Technical Paper / dx.doi.org/10.13182/NT65-A20580
A Nuclearly Safe Triangular-Slab Tank for Handling Enriched Uranium
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 546-547
Technical Paper / dx.doi.org/10.13182/NT65-A20581
Gamma-Ray-Induced Chlorination of Benzene
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 548-555
Technical Paper / dx.doi.org/10.13182/NT65-A20582
Production of Carrier-Free 132Cs and 129Cs
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 556-559
Technical Paper / dx.doi.org/10.13182/NT65-A20583
Pyrolytic-Carbon Coatings on Ceramic Fuel Particles
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 560-566
Technical Paper / dx.doi.org/10.13182/NT65-A20584
Fluidized-Bed Process for Production of Tungsten
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 567-574
Technical Paper / dx.doi.org/10.13182/NT65-A20585
Vapor Deposition and Characterization of Tungsten-Rhenium Alloys
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 575-580
Technical Paper / dx.doi.org/10.13182/NT65-A20586
Suppression of Grain Growth in Vapor-Deposited Tungsten up to 2500°C
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 581-583
Technical Paper / dx.doi.org/10.13182/NT65-A20587
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 584-588
Technical Paper / dx.doi.org/10.13182/NT65-A20588
Fabrication of 20wt%Ti-V Alloy Tubing for Nuclear Fuel Cladding
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 589-596
Technical Paper / dx.doi.org/10.13182/NT65-A20589
Absolute Liquid-Scintillation Rate Constants and Fluorescence Efficiencies
Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 597-602
Technical Paper / dx.doi.org/10.13182/NT65-A20590